ML20024G320

Proposed Tech Specs to Stipulate Means by Which Safety/ Relief Valve Operability Verified

ML20024G320
Person / Time
Site:	Monticello
Issue date:	03/08/1977
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G317	List: ML20024G316 ML20024G318 ML20024G320
References
NUDOCS 9102110293
Download: ML20024G320 (2)

Text

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k License Amendment Request Dated March 8,1977 Dthibit B This exhibit consists of the following page revision

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3 to incorporate all of the proposed Technical Specification Changes:

Page 105

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D 30 LIMITING CONDITIONS. FOR OPERATION h.O SURVEILIN CE REQUIREMEITS

-1. Except as specified in 3.5.E.2 and 1. Testing:

3 5.E.3~ below, the entire auto =atic pressure relief sy:: tem shall be operable Item Frequency-'

- at any time the reactor pressure is above Valve operability Each operating cycl 150 psig and irradiated fuel is in the reactor' vessel.-

Simulated automa-- Each operating cycle  ;

tic actuation' test i

2. From and after the date that one of the autorntic pressure relief system valves is NOTE: Safety / relief valve operability made or found to be ' inoperable for any is verified by c.ycling the valve and observing a compensating.

reason, reactor operation 'is .pemissible change in turbine bypass valve I only during the succeeding seven_ days position.

l unless such valve is sooner made operable, l provided that during such seven days 2. When it is determined that one or both remaining automatic relief system more aatomatic pressure relief valves valves and' the IIPCI system are operable. of the Automatic Pressure Relief system is inoperable, the HPCI systen -

3 From and after the date that more than shall be demonstrated to be operable one c,f the automatic pressure relief immediately and weeitly thereafter.

valves are made or found to be inoperable for any reason, reactor operution _is h

permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless repairs are made and .

provided that during such time the HPCI system is operable.

4 If the requirements of 3.5.E.1-3 cannot be met, an orderly reactor 35/4.5 los nEv

,a 195 m u.s. NuCLt AR RtoutATony C SSloN DOCKET NUMIE A L) 50-263 NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL '""*"'"

' TO: FROM: DATE OF DOCUMENT Northern States Power Company 3/8/77 Mr. Victor Stello Minneapolis, Minnesota oATE RECElvEo L. O. Mayer

• 3/10/77 EE TTE R WNOToRIZED P R OP INPUT FORM NUMBE R OF Co#lES RECEIVE D

@oRniNAL $UNC LASSIFIE o Three signed UCOPY 37 Copies enc 1. reCYd.

l oEsCRIP TION ENCLoSU RE Ltr re our 1/5/77 ltr...trans the follawing: Andt. to ol/notorized 3/8/77'/ change _to l Appendix A tech specs..Concerning the' automatic pressupe relief" system......

PtAnr uAME: (1-P) (4-P)

" "'ic* ACKNOWIsEDGED .

DO NOT REMOVE SAFETY FOR ACTION /INFORMATION rWTnn 3/10/77 -

RJL ASSIGNED AU: -

ARSENEDJn.

3 RANCH CHIEF; Ziemann (T) RMHCH_CHTrr.

JROJECT_rMNAGER.:_ Snaider PROJECT MANAGER:

IIC. ASST. Dizzs LIC,_ ASST. :

$ $ d h o t' A W

_ ,s INTERNAL DISTRIBUTION iREGFILEJ SYSTEMS SAFETY PLANT SYSTEMS SITE SAEETLS NRc ruk _ . HEINEMAN TEDESg_0 ENVIRO Af{ALYSIS  !

>( I6E (*) SCHROEDER BENAROYA DENTON & MUT T rn  !

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SITE TECH.

PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH. CAMIILL BOYD P, COLLINS EOSS X EISENHUT (4 7A.) '

STEPP NOVAK HULMAN l HOUSTON ROSZTOCZY M_SIIA0 l PETERSON X BAER CHECK k_ BlTTLER SITE ANALYSIS l MELTZ 'g _ cgittgS,_, VOLLMER HELTEMES AT & I '

BUNCH SKOVHOLT SALTZMAN X J. COLLINS RUTBERG KREGER l EXTERNAL DISTRIBUTION CONTROL NUMBER MPDR: Minnnanniin. Mint .

NAT _ LAB: _BR00KilAVEN3U IAR, X TIC: REG V.IE ULRIK_ SON (ORNL) 8 NSIC: LA PDR ggg

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